Back-End of the Fuel Cycle: Spent Nuclear Fuel and Irradiated Materials
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MODULE 6.0: BACK-END OF THE FUEL CYCLE: SPENT NUCLEAR FUEL AND IRRADIATED MATERIALS Introduction Welcome to Module 6.0 of the Fuel Cycle Processes Directed Self-Study Course! This is the sixth of nine modules available in this directed self-study course. The purpose of this module is to provide an understanding of nuclear fuel and materials after their use for generating power in a reactor - referred to as the “back-end” of the fuel cycle - and the differences between the open and closed fuel cycles. Unlike the other parts of the fuel cycle, the spent nuclear fuel (SNF) is highly radioactive and heat-generating; and thus, the facilities, hazards, and safety approaches are fundamentally different. The module has seven learning objectives. This self- study module is designed to assist you in accomplishing the learning objectives listed at the beginning of the module. The module’s self-check questions will help you assess your understanding of the concepts presented. Before you Begin It is recommended that you have access to the following materials: ◙ Trainee Guide Complete the following prerequisites: ◙ Module 1.0: Overview of the Nuclear Fuel Cycle ◙ Module 5.0: Fuel Fabrication How to Complete this Module 1. Review the learning objectives. 2. Read each section within the module in sequential order. 3. Complete the self-check questions and activities within this module 4. Check off the tracking form as you complete the self-check questions and/or activity within the module. 5. Contact your administrator as prompted for a progress review meeting. 6. Contact your administrator as prompted for any additional materials and/or specific assignments. 7. Complete all assignments related to this module. If no other materials or assignments are given to you by your administrator, you have completed this module. 8. Ensure that you and your administrator have dated and initialed your progress on the tracking form. 9. Go to the next assigned module. 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MODULE 6.0: BACK-END OF THE FUEL CYCLE: SPENT NUCLEAR FUEL AND IRRADIATED MATERIALS TABLE OF CONTENTS LEARNING OBJECTIVES ................................................................................................................. 6-1 OVERVIEW OF BACK-END OF THE FUEL CYCLE ............................................................................ 6-1 SNF PROPERTIES........................................................................................................................... 6-5 Burn-Up .................................................................................................................................. 6-12 SNF STORAGE ............................................................................................................................. 6-13 Wet Storage of Spent Fuel ..................................................................................................... 6-13 Dry Storage of Spent Fuel ...................................................................................................... 6-15 Self-Check Questions 6-1 ....................................................................................................... 6-19 SNF REPROCESSING ................................................................................................................... 6-21 Wet Reprocessing Routes ...................................................................................................... 6-23 Dry Reprocessing Routes ....................................................................................................... 6-25 Reprocessing Facilities ........................................................................................................... 6-25 NRC REGULATIONS FOR REPROCESSING FACILITIES.................................................................. 6-26 REPROCESSING ENVIRONMENTAL, SAFETY, AND HEALTH CONCERNS, AND SAFETY APPROACHES.............................................................................................................................. 6-27 SNF RECYCLE .............................................................................................................................. 6-28 Self-Check Questions 6-2 ....................................................................................................... 6-30 HIGH LEVEL WASTE (HLW) ......................................................................................................... 6-32 Vitrification ............................................................................................................................ 6-33 Transmutation ........................................................................................................................ 6-36 REPOSITORY FOR HLW AND SNF ............................................................................................... 6-37 Self-Check Questions 6-3 ....................................................................................................... 6-48 ONGOING PROGRAMS ............................................................................................................... 6-51 Costs ....................................................................................................................................... 6-52 NRC INVOLVEMENT ................................................................................................................... 6-53 MODULE SUMMARY .................................................................................................................. 6-56 USNRC Technical Training Center 3/10 Rev 4 i Fuel Cycle Processes Directed Self-Study Course MODULE 6.0: BACK-END OF THE FUEL CYCLE: SPENT NUCLEAR FUEL AND IRRADIATED MATERIALS List of Figures Figure 6-1. SNF Assembly Being Removed During Refueling ...................................................... 6-2 Figure 6-2. SNF Options and Decision Tree ................................................................................. 6-3 Figure 6-3. Example of SNF Constituents .................................................................................... 6-6 Figure 6-4. Distribution of Fission Products from Uranium-235 ................................................ 6-7 Figure 6-5. Radioactive Decay of Fission Products ..................................................................... 6-8 Figure 6-6. Isotopic Breakdown of SNF Radioactive Decay ........................................................ 6-9 Figure 6-7. Typical SNF Assembly Heat Generation .................................................................. 6-11 Figure 6-8. SNF Burn-Up Trends in the United States .............................................................. 6-12 Figure 6-9. SNF Burn-Up Trends Worldwide ............................................................................. 6-13 Figure 6-10. Typical SNF Storage Pool at a Reactor .................................................................. 6-14 Figure 6-11. Large SNF Wet Storage Pools at La Hague, France ............................................... 6-15 Figure 6-12. Vertical Dry Storage Showing Air Inlets and Outlets ............................................ 6-17 Figure 6-13. Horizontal Modules for Dry Storage of SNF ......................................................... 6-17 Figure 6-14. Purex Process Flow Diagram ................................................................................. 6-24 Figure 6-15. THORP in the UK ................................................................................................... 6-26 Figure 6-16. HLW Integrated Repository Heat Loads ............................................................... 6-32 Figure 6-17. HLW Cans In Cell ................................................................................................... 6-33 Figure 6-18. UK Vitrified HLW Storage ...................................................................................... 6-34 Figure 6-19. Typical HLW Can ................................................................................................... 6-35 Figure 6-20. Fission Transmutation .......................................................................................... 6-37 Figure 6-21. Transmutation of Iodine ....................................................................................... 6-37 Figure 6-22. Aerial View of Yucca Mountain ............................................................................. 6-40 Figure 6-23. Exploratory Tunnel Entrance ................................................................................ 6-40 Figure 6-24. Tunnel Boring Machine (TBM) .............................................................................. 6-41 Figure 6-25. Schematic of Access and Emplacement Tunnels at Yucca Mountain .................. 6-42 Figure 6-26. Repository Heat Rate ............................................................................................ 6-43 Figure 6-27. Temperature Estimates - Direct Disposal of SNF .................................................. 6-44 Figure 6-28. Temperature Estimates - GNEP SNF/HLW ............................................................ 6-44 Figure 6-29. SNF Decay Heat - No Reprocessing ....................................................................... 6-45 Figure 6-30. Reprocessing Effect on Major Isotopes ................................................................ 6-45 Figure 6-31. Reprocessing Effect on Heat Load ........................................................................ 6-46 Figure 6-32. Dose